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NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT

Energy Reorganization Act of 1974 +  and Atomic Energy Act of 1954 +

Iodine +, Cesium +, Nitrogen +, Oxygen +, Hydrogen +  and Lead +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 20.407 +  and 10 CFR 20.408 +

00247  +, 00369  +, 00267  +, 00416  +  and 00271  +

Reactor Trip +  and Turbine Trip +

Massaro S +  and NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) +

NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 82-16, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-40, Operator Licensing Examination +, NRC Generic Letter 83-36, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-33, NRC Positions on Certain Requirements of Appendix R to 10 CFR 50 +, NRC Generic Letter 83-02, NUREG-0737 Technical Specifications +  and NRC Generic Letter 83-01, Operator Licensing Examination Site Visit +

ML20092F172 +, ML20092F172 +, ML20092F172 +, ML20092F172 +, ML20092F172 +, ML20092F172 +  and ML20092F172 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

Westinghouse +, General Electric +  and Target Rock +

NRC Bulletin 79-15 +, NRC Bulletin 82-03 +, NRC Bulletin 83-01 +, NRC Bulletin 83-02 +  and NRC Bulletin 83-07 +

NUREG-0871 +, NUREG/CR-3568 +, NUREG/CR-2000 +, NUREG/CR-3049 +, NUREG/CR-3430 +, NUREG-0304 +, NUREG/CR-3540 +, NUREG/CR-3416 +, NUREG-0485, Forwards 780922 NUREG-0485, Status Summary Rept,Sep. W/O Encl +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0981, Forwards Matl Prepared for Limerick & Indian Point Hearings Per 850123 Request & NRC Documents Ref During Discussions. Jan 1985 Seismogeological Siting Criteria & Guidelines, Forwarded to L Reiter +, NUREG-0936, Provides Copy of NUREG-0936,Vol 17,Number 2, NRC Regulatory Agenda Semiannual Rept July - Dec 1998, in Response to Request Raised by C Rogers During Oct 1998 All Agreement States Meeting +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0957, Forwards Copy of NUREG-0957, Price-Anderson Act-Third Decade. W/O Encl +, NUREG-1024, Forwards Update of 861121 CRGR Package Re Proposed Generic Ltr on short-term Tech Spec Improvements.Comments from AEOD, IE & Ofc of General Counsel Incorporated in Update or Resolved.Res Concurred W/O Specific Comment +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, NUREG-0713, Vol.43, Occupation Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2021: Fifty-Fourth Annual Report +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0554, Responds to to Chairman Jackson Re Resolution of Berkeley Township Environ Commission. Forwards Reply to L Worrall Which Contains Directors Decision,Per 10CFR2.206 +, NUREG-0020, Responds to Encl Re Spent Fuel Storage Capacity at Plant.Spent Fuel Pool at Plant Has Sufficient Space to Accommodate Addl Fuel Storage Racks of Current Design +, NUREG-0540, Notifies of Issuance of NUREG-0568, Title List of Publicly Available Documents on Tmi,Docket 50-320. Suppl Will Be Published.All New Entries Will Be in NUREG-0540,Title List Journal,Issued Monthly +, NUREG-0995, Safety Evaluation Re Restart of Facilities.Licensee Acceptably Revised & Expanded Surveillance Testing Programs to Address Reactor Trip Issue +, NuREG/CR-2987 +, NUREG/CR-3458 +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-0090, SECY-25-0016: Enclosure 1 - NUREG-0090, Volume 47, Report to Congress on Abnormal Occurrences: Fiscal Year 2024 +

Automatic Scram +  and Manual Scram +

Texas +, Tennessee +, Pennsylvania +, Connecticut +, Georgia +, Illinois +, Colorado +, Minnesota +, North Carolina +, Washington +, California +, Massachusetts +, Alabama +, New Jersey +, New York +, Michigan +, Florida +, Louisiana +, Mississippi +, Nebraska +, Vermont +, Iowa +, Delaware +  and Alaska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Containment Spray +  and Extraction steam +

Safe Shutdown +, High winds +, Shutdown Margin +, High Radiation Area +, Hydrostatic +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Commercial Grade +, Control of Heavy Loads +, Fuel cladding +, Flow Induced Vibration +, Unidentified leakage +  and Overexposure +